ML20215D472
| ML20215D472 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/11/1987 |
| From: | Tiernan J BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8706190025 | |
| Download: ML20215D472 (25) | |
Text
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BALTIMORE GAS AND -
ELECTRIC CHARLES CENTER R O. BOX 1475 BALTIMORE, MARYLAND 21203 I JOSEPH A.TIERNAN VecE PnEslDENT NUCLEAR ENEnOY June 11,1987
.U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: ' Document Control Desk SUBJEC' T:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317.& 50-318 Compliance with 10 CFR 50.62, Reduction of Risk from ATWS Events
REFERENCE:
(a)
Letter from Mr. 3. A. Tiernan (BG&E), to Mr. A. C. Thadani (NRC),
dated June 27,1986, same subject Gentlemen:
.The ATWS Rule,10 CFR 50.62, requires that hcensees provide sufficient information to verify compliance with the rule. In June 1986, we detailed how we intend to comply (Reference a).'
We provided you with more information in a meeting with members of your staff on' April 1,1987. While most of the outstanding issues were resolved at that meeting, we agreed to provide further information to resolve the few that remained.
The attachments provided with this letter, along with our discussions on April 1,1987, should provide you with sufficient information to verify our compliance with the rule.
Should you have any additional questions regarding this matter, we would be pleased to discuss them with you.
Very truly yours, 6
M JAT/ WPM / dim Attachment cc:.. D. A. Brune, Esquire
- 3. E. Silberg, Esquire f
R. A. Capra, NRC
((;h S. A. McNeil, NRC i)
W. T. Russell, NRC T. Foley/D. C. Trimble, NRC 8706190025 870611 DR ADOCK 050 7
,1 ATTACHMENT A POWER SUPPLIES The NRC Staff considers a station battery, not used to provide power to reactor trip system (RTS) components,'to be a preferred source for providing power to diverse scram eystem (DSS) and diverse turbine trip (DTT) logic and actuation devices. However, a bus
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used to provide power to RTS loads may also be used to provide power to DSS or DTT circuitry provided:
faults within the DSS or DTT circuitry cannot degrade the reliability / integrity j
of the existing RTS below an acceptable level, and l
1 a common cause (mode) failure mechanism affecting the RTS power distribution system (including degraded voltage conditions such as overvoltage and undervoltage) cannot compromise both the RTS and DSS functions.
(From: Letter from D. M. Crutchfield, to R. C. L. Olson, Status of the CE Owners Group Conceptual Design Review, June 6,1986).
Our proposed design for the DSS, DTT, and diverse auxiliary feedwater actuation system (AFAS) will use the existing reactor protective system (RPS) power supply. The RPS
. power supply consists of four safety-related,120 volt vital AC busses. A simplified block diagram was provided_ to you during the meeting on April 1,1987. In the preliminary stages of design, we decided to use the existing RPS power supply to maximize the
'i reliability of the ATWS power supply. We believe the design of the RPS power supply I
also minimizes the potential for common mode failure.
d Faults within the DSS, DTT, and AFAS will not degrade the reliability or integrity of the RPS. The DTT and AFAS systems are original plant systems with a history of reliability and the new DSS system will use existing Engineered Safety Features Actuation System (ESFAS) equipment. The ATWS design does not change or affect the existing RPS power source configuration. Separately fused 120 VAC circuits from separate vital 120 VAC busses will be used to power each channel of each of these systems.
The vital power source design minimizes the possibility that a common mode failure would compromise both the RPS and DSS functions. To determine the potential impact of RPS/ DSS power source common mode failure, the following cases were considered.
Total Loss of Voltage
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i Overvoltage Condition i
l Undervoltage Condition Total Loss of Voltage A total loss of voltage will not compromise both the RPS and the DSS. A loss of voltage at any point in the power distribution system will not prevent both systems from functioning. A total loss of voltage at the 125 VDC or 120 VAC vital busses would result in an immediate reactor trip via Trip Circuit Breaker UV-trip Devices (DC) or RPS K relays (AC). I
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ATTACHMENT A -
g POWER SUPPLIES h,
Overvoltane Condition Table i lists the protective features (trips, alarms, Indications) that are available to mitigate an overvoltage condition.
Overvoltage in the 125 VDC or 120 VAC systems would most likely originate in the -
chargers because they are the potential source of a higher than normal voltage.
Charger input is 480 VAC. The regulating capabilities of downstream equ".pment (inverters and power supp!!es) mitigate this condition. The following sequence of events illustrates an overvoltage condition.
' l.
125 VDC bus at normal voltage (about 132 VDC) b
- 2. - Charger Failure - Bus voltage begins increasing -
3.
140 VDC - Inverter output begins increasing (from 120 VAC) -
' a.
-125 VAC - RPS power supply output begins increasing
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b.
132 VAC - DSS power supply' output voltage begins increasing 4.
150 VDC - Battery Charger Overvoltage Alarm
- 5. - If the overvoltage condition increases further, to the point that equipment failures resul3 (blown fuses, damaged solid state devices, etc.), this will result
'In RPS channel trips and reactor trip.
Undervoltase Condition '
mc Table I lists the protective features (trips, alarms, Indications) that are available to h '.
' mitigate an undervoltage condition.
Undervoltage is the more credible failure mode and can originate at any point in the power system. The following is an example of a sequence of events on an undervoltage condition la the 125 VDC system.
u
- 1. : 125 VDC bus at normal voltage (about 132 VDC) 2.
Battery lost r;r disconnected - Battery monitor alarms 3.
Failure of chargers - Bus voltage begins dropping off l
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123 VDC - 125 VDC Bus Undervoltage Alarm 5.
120 VDC - 125 VDC Battery Charger Undervoltage Alarm 1
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' ATTACHMENT A.
POWER SUPPLIES 6.
105 VDC - Inverter output begins dropping off '(from 120 VAC) 105 VAC RPS/ESFAS (DSS) power supplies outputs begin dropping off a.
up b.
'100 VAC - RPS K relays trip reactor' trip breakers Undervoltage conditions originating in' the 125 VDC or 120 VAC systems are of greatest, concern from a common mode standpoint; however, the - undervoltage-4
. alarm setpoints on the DC busses and charger outputs cause alarms well before the 3$
voltage level is low enough to prevent system operation.
' The RPS and' ATWS power sources are controlled by the Technical Specifications.
Technical Specifications 3.8.1.1, 3.8.1.2, 3.8.2.1, 3.8.2.2, 3.8.2.3, and 3.8.2.4 cover the operational and surveillance requirements for. these systems. The protective and alarm relays for these systems are covered by a preventive rr.alntenance program which checks
- setpoints and calibrates the relays on a refueling basis.
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ATTACHMENT B ISOLATION DEVICES Your request for additional information stated in part:
Information must be provided to demonstrate the adequacy of all isolation devices used to protect the integrity of safety related circuits from non-safety related ATWS circuits. The required information is identified in Attachment 2.
If the isolation devices are identical to isolation devices used in other applications (e.g.,
to isolate the safety parameter display system from safety related circuits), and the requested information has been previously submitted for staff review, and the isolation devices have been approved for their applications, the related correspon-dence should be referenced, and no additional information need be provided.
At the April 1,1987 meeting, we provided the information requested under the title ATWS Isolation Devices (copy attached). We feel these isolation devices, which are currently approved for use in our Engineered Safety Features Actuation System (ESFAS),
are adequate for ATWS isolation devices. In accordance with your request for additional information, we need not provide the information requested under Attachment 2 to your request. However, we have provided additional information, obtained from the vendor of the ESFAS actuation relays, concerning their isolation capabilities.
The ESFAS actuation relays, GE Model 3SAA1383A2, are miniature, canned, mil quality power relays. The relay has an eight pin configuration. Pins 2 and 7 are the primary (coll) connections (28 VDC for ESFAS, DDS, and DTT). Pins I to 3 (or 8 to 6) are nor-mally open output contacts used by DTT (125 VDC). Pins 1 to 4 (or 8 to 5) are normally closed output contacts used by DSS (240 VAC).
The DTT is an existing system that has been in place from initial plant startup. The maximum credible faults for this circuit (turbine trip) are set by circuit fusing,30 amps, and maximum credible DC bus voltage 150 VDC. The proposed DSS M/G contactor trip circuit has maximum credible faults of 300 VAC (overvoltage trip point of M/G set) and 10 amps by circuit fusing.
The ESFAS initiation relays (GS Model 3SAA1383A2) are tested by the manufacturer to insure 10,000 meg ohms minimum insulation resistance between primary (coil) and secondary (output) and between adjacent contacts. Also, the relays are subjected to a 1500 volt, 60 Hz AC Hi Pot Test from primary to secondary, across normally open contacts, and from all contacts to relay can. Finally, the output contacts are tested to insure a maximum contact resistance of 0.050 ohm (new) and 0.100 ohm after life testing.
These relays are part of the original design of the ESFAS system and meet the environmental and seismic qualification of this system.
The DSS M/G set contactor trip circuit wiring from ESFAS actuation relay output contacts to cabinet field cable terminal strips will be routed separate from existing ESFAS actuation wiring and routed in flexible conduit rather than existing wiring bundles.
These relays are powered from ESFAS cabinet 28 VDC power supplies which receive power from lE vital 120 VAC busses. J
4 ATTACHMENT B ISOLATION DEVICES
.a Prior Approval of ATWS isolation Devices 1
FSAR Section 7.3.1.1:
The design of the engineered safety features actuation systems and component parts was based on the applicable requirements of IEEE-279 Criteria for Protection Systems for Nuclear Power Generating Stations.
Electrical isolation has been provided between redundant channels, between sensor and actuation subsystems, and between the engineered safety features actuation system and ancillary equipment.
Where electrical isolation is provided, an application of short circuit, open wire, ground, or potential does not inhibit a protective action as a result of the failure of the redundant system. (Emphasis added.)
The NRC questioned our design further (Q 7.3.1):
]
Provide identification of those features of the design that do not conform to the criteria of IEEE-279... and an explanation of the reasons for these.
Our answer:
All protection systems that actuate reactor trip and engineered safety features components are designed to conform to the criteria of IEEE 279...
IEEE-279:
4.7.2 Isolation Devices. The transmission of signals from protection system equipment for control system use shall be through isolation devices which shall be classified as part of the protection system and shall meet all the requirements of this document. No credible failure at the output of an isolation device shall prevent the associated protection system channel from meeting the minimum performance requirements specified in the design bases.
NRC Safety Evaluation Report Section 3.2.4.2:
Those portions of the reactor protection system and the actuation systems for engineered safety features supplied by Combustion Engineering are functionally identical to the Maine Yankee plant protection systems. Combustion Engineering used IEEE-279 as a guide in the design of both of these systems. The applicant states that those features of the reactor protection systems and the engineered safety features actuation systems that are not of Combustion Engineering design meet or exceed the criteria of IEEE-279...
We have reviewed the design of the plant protection system and have concluded that it conforms to the applicable criteria and is acceptable. (Emphasis added.).
4 4
. ATTACHMENT C.
- ATWS SYSTEM RELIABILITY
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AT.WS System ' Reliability. will be proven _and maintained by coordinating the existing i
. Surveillance Testing and Preventive Maintenance Program of RPS, AFAS, and ESFAS to include DSS and DTT.--
The following surveillance philosophies currently apply to RPS, AFAS, ESFAS, and will be applied to DSS and DTT if applicable.
1.
Daily (at least once per shif t) channel checks of pressurizer' pressure and S/G 1evel.
2.
. Monthly channel functional testing.
3.-
Refueling interval calibration to include entire' instrument loop (sensor, bistable, indications, etc.).-
4.'
Refueling interval integrated system testing including final actuation device.
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R
F ATTACHMENT D REVISION TO THE
SUMMARY
PROVIDED AT APRIL 1,1987 MEETING i
10 CFR 50.62 REDUCTION OF RISK FROM ATWS EVENT
SUMMARY
OF DIVERSITY BETWEEN THE REACTOR PROTECTIVE SYSTEM AND THE DIVERSE SCRAM SYSTEM AND THE DIVERSE TURBINE TRIP SYSTEM FOR CALVERT CLIFFS NUCLEAR POWER PLANT UNITS 1 AND 2 i
Pags No.'i 03/20/87
SUMMARY
10 CFR 50.62 REDUCTION OF RISK FROM ATWS EVENTS REACTOR PROTECTIVE SYSTEM, DIVERSE SCRAM SYSTEM AND DIVERSE TURBINE TRIP COMPOSITE OF DIVERSITY COMPARISON DSS DTT COMPONENT-COMPONENT FUNCTION FUNCTION COMPONENT DIVERSITY DIVERSITY NOTES
=
=
=
=
Sensors No Yes 1,2 Isolators Yes Yes 1,3,4 Bistables Yes Yes 5
Coincident Logic Yes Yes 5
Initiation Relay Yes Yes 6,7 Final Trip' Device Yes Yes 8,9 OVERALL DIVERSITY CONCLUSION Calvert Cliffs, Units 1 and 2 comply with the ATWS rule in terms of diversity.between the reactor trip function and the diverse scram function and the turbine trip function. This is due to the design and.
functional diversity ~between the systems.
i
Page No.
$1
.03/23/87 10 CFR 50.62 REDUCTION OF RISK FROM ATWS EVENTS REACTOR PROTECTIVE SYSTEM, DIVERSE SCRAM SYSTEM AND DIVERSE TURBINE TRIP DIVERSITY COMPARISON NOTES for
SUMMARY
and TABLE 1:
' 1.
The ATWS RULE requires diversity only from the sensor output. The DSS. shares the same sensor loops as the RPS; however, the DSS bistable and logic circuits are isolated from the RPS circuits via Class.IE isolators (see ' isolators')
which are considered to be the first component in the DSS /RPS diversity comparison.
2.
Diversity exists for the DTT CEDM Bus UV sensors and intermediate sensor relay due to differences in design principle, power source and function. Although G.E.
relays are used in the RPS initiation circuit (see Table 2), they are a different model (NGV vs ICR &
HFA for DTT), different design principles and operating voltages (120VAC vs 240VAC & 125VDC respectively).
The power source for the U.V.ICR relay is the same AC source which is used for the RPS
' Final Trip device' ie. 240V,3 phase-MG 1 & 2 power to the CEDMCS
-for the DTT this source also functions as the measured variable.
3.
Diversity exists for the DTT Sensor Isolators due to differences in design principles, DC power source and function.
Although Clare relays are an integral part of the RPS bistables, they are-a different model (HGSM for RPS vs HFW for DTT), different design principles and operating voltage (15 VDC vs 40 VDC respectively).
The RPS-HGSM relay deenergizes to trip, while the DTT-HFW relay energizes to trip (see Table 2).
4.
Diversity exists for the DSS Sensor loop Isolator due to the fact that no comparable devices exist in the RPS system. The isolators are listed in this comparison to show that Class IE isolation is employed to seperate the DSS circuits from the RPS sensor loop;
5.
Diversity exists for the DSS & DTT Bistables & Coincident Logic due to differences in manufacture, design principles, DC power source and DC power supply manufacturer.
6.
Diversity exists for the DSS & DTT' Initiation Relays due to the differences in model. design principles power source and function.
A]though all the relays are G.E. manufacture, the models numbers and design principles are different (ie. RPS-NGV type in draw out
(
case vs DSS /DTT - hermetically sealed plug-in type); operating j
voltages (RPS - 120VAC vs DSS /DTT - 28VDC) and function (ie. RPS-deenergize to trip vs DSS /DTT - energize to trip) are different
)
(see Table 2).
7.
The Unit 1 DTT system is equipped with two ' intermediate' relays
)
in the initiation circuit. These are located in the Turbine EHC cabinet and are called the
'Ist Hit Customer Trip Relay' and the
' Master Trip Relay'.
Notes continued on Page No. iii
. Pege No. iii -
03/23/87 10 CFR 50.62 REDUCTION OF RISK FROM ATWS EVENTS REACTOR PROTECTIVE SYSTEM, DIVERSE SCRAM SYSTEM AND DIVERSE TURBINE TRIP DIVERSITY COMPARISON NOTES for
SUMMARY
and TABLE 1:
7.
(cont'd) l Diversity exists for the
'ist Hit' relay due to differences in model, function and operating voltage.
Although the manufacturer is the same as in the RPS Bistables (eg. Clare),
the model and operating voltage (RPS-15VDC dual coil bistable vs DTT-125VDC single coil self-reset) and function (ie.RPS - deenergize to trip vs DTT - energize to trip) establish the required diversity (see Table 2).
Diversity exists for the
' Master Trip' relay due to differences in model no.,
design principle, operating voltages and DC power supplies. The G.E. type CR120 relay for DTT is a different model and design principle than the G.E. type NGV relay used in the RPS initiation circuit; operating voltage (120VAC -RPS vs 24VDC -DTT) and AC power source (120VAC vital - RPS vs 120VAC non-vital -DTT) differences further enhance the diversity (see Table 2).
8.
Diversity exists for the DSS Final Trip Device due to differences in model, design principles and operating voltage.
Although the manufacturer is G.E.
for both the RPS & DSS, the RPS is a circuit breaker while the DSS device is a contactor; the circuit breaker operating voltage (ie.
trip coil & close coil) is 125 VDC while the contactor operating voltage is 240 VAC for the aux. relay and a rectified 240 V for the contactor coil.
9.
Diversity exists for the DTT Final Trip Device due to differences in type, model, design principle and operating voltage (Unit 1).
Athough G.E.
is the manufacturer for both the Unit 1 DTT device and the RPS device, diversity is established by the design principle difference (eg.
RPS circuit breaker vs DTT solenoid valve) and operating voltage (125VDC - RPS vs 24VDC - DTT).
For Unit 2 the solenoid valve is manufactured by Westinghouse, which further establishes the diversity, even though the DC power source is the same for Unit 2 DTT and the RPS Final Trip devices.
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'l 103/27/87-10 CFR~50 62 REDUCTION OF RISK FROM ATWS EVENTS RPS DSS AND DTT DIVERSITY COMPARISON TABLE 2 I
SYSTEM TAG NO.
MODEL NUMBER FUNCTION DATA
============================ ;=======================_===================___
50 MANUFACTURER:-GENERAL ELECTRIC CO.
j RPS.
K1',K2,K3 12NGV13A1A INITIATION HI SPEED.AC UNDERVOLTAGE RELAY, 1
.K4 RELAY 120VAC OPERATED HINGED-ARMATURE l
TELEPHONE TYPE, DIODE BRIDGE.FOR AC.
APPLIC. 2N.O.&2N.C. CONT'S,S1 CASE 9 1/8"X6 5/8"X7 1/2", WT.10LBS; DSS
- XK119, 3SAA1383A2 INITIATION MINIATURE, PLUG-IN OCTAL SOCKET XK120 RELAY E-FRAME MAGNET,28VDC,DPDT 10A CONT DTT
.XK103 1.67"X1.48"X2.1",WT.4.50Z
.DTT 27-1,-2, 12ICR54B2A UNDERVOLATAGE-3 PH. VOLTAGE OPER'D INDUCTION-DISK 27-3,-4 RELAY TIME DELAY (0.17sec)-RESPONDS TO PH SEQUENCE.OPEN PH.OR U.V.,240VAC OF FIELD SET @ 216V, 1 N.O.& 1 N.C.
10 5/16"X6 5/8"X6 3/4",WT.12LBS.
DTT.
UV1,UV2, 12HFA151A2F U.V. RELAY MULTICONTACT AUXILIARY RELAY,6N.O..
UV3,UV4 CODE 06 CONTACT MULTI. CONTACTS,125VDC COIL, OPER. TIME =-
RELAY 5 CYCLES,SELF-RESET,REOSTAT ADJ.
CAL. RANGE 70-100V SEMI-FLUSH MTG.
6 1/2"X7"X5 3/16",WT.5LBS l
DTT
'XKT1000 CR120HF47J10 INTERM. INIT.
GEN. PURPOSE RELAY, 11 FIN RECT.
. RELAY PLUG-IN, 24VDC COIL, DUST COVER,
' MASTER TRIP' DPDT 10A CONTACTS 2.12"X2.06"X1.44" I
i
~
1 e
)
a
.Pege No.'
2 03/27/87-
.10 CFR 50.62 REDUCTION OF RISK FROM ATWS EVENTS j
RPS, DSS AND DTT DIVERSITY COMPARISON TABLE 2 i
l SYSTEM TAG NO.
MODEL NUMBER FUNCTION DATA
.======================================================== ===
1
-c* MANUFACTURER: CLARE RPS K1,K2,K3 HGSM51113R01 BISTABLE & 2/4 MINIATURE PLUG-IN, METAL CASE,MERC.
LOGIC RELAY WETTED CONTACT, HERMETICALLY SEALED 1
DUAL COIL-BISTABLE,10VDC MIN.OPER.
1250 OHM WINDG,2A.100VA,500V CONT.
)
MIN.OPER @ 7.2MA,RELE @ 1.8MA DTT XK9 HFW1201K01 CEDM BUS MFGR. COMM. INSTRUMENT INC., HALF-~.
s U.V. SIGNAL SIZE ~ CRYSTAL CAN, WELDED, HERMETICAL
)
ISOLATION LY SEALED ENCL,.187"PCB/ PLUG-IN 4
26VDC COIL DPDT BIFURCATED HARDNED SILVER ALLOY CONT,.81"X.41"X.41" i
DTT KT823 HGSM51111VOO INTERMEDIATE MINIATURE PLUG-IN. METAL CASE,MERC.
l INIT. RELAY WETTED CONTACT HERMETICALLY SEALED
'1ST HIT' SINGLE COIL,48 VDC,8600 OHM WINDNG 2 AMP,100VA,500V CONTACTS. MIN.OPER
@ 2MA,RELE @.5MA,.64"X.64"X2.08" I